99mTc is the most widely used radionuclide in medical diagnostics and typically obtained from high-specific-activity (HSA) 99Mo produced in nuclear reactors. However, recent reactor shutdowns have led to supply shortages and prompted efforts to implement alternative production methods. One promising approach is neutron activation of 98Mo, which yields low-specific-activity (LSA) 99Mo. Since conventional Al2O3-based 99Mo/99mTc generators are designed for HSA 99Mo, adaptations are required for LSA 99Mo usage. In this study, we evaluated the feasibility of modifying existing Al2O3-based 99Mo/99mTc generators for use with LSA 99Mo, anticipating production at the planned high brilliance neutron source (HBS) at Forschungszentrum Jülich. Key modifications included adjustments to the amount of Al2O3 on the column and the elution volume of 99mTc to enhance 99Mo adsorption and 99mTc elution efficiency. The performance of the modified “mock-up” system was compared with a standard clinical generator. The results demonstrated that only minor modifications are required for LSA 99Mo to be effectively utilized in a future generator, with elution efficiencies remaining comparable to conventional generators, while maintaining parameters like size, form, number, activity of the individual generator comparable. However, 99Mo breakthrough levels exceeded regulatory limits, highlighting the need for further optimization. Nevertheless, these findings support the feasibility of using LSA 99Mo in clinical applications with minimal changes to existing infrastructure.

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